Published March 1990
| Version v1
Journal article
Results of thermal stratification tests in a horizontal pipe line at the HDR-facility
Creators
- 1. Valtion Teknillinen Tutkimuskeskus (Finland)
- 2. Kernforschungszentrum Karlsruhe GmbH (Germany, F.R.)
Description
Global and local stresses of the pipe wall have been analyzed based on the HDR thermal stratification experiments, existing of the simulation of typical feedwater stratification phenomena in both pressurized and boiling water reactors. The measured global stresses due to the wall temperature differences have been compared to analytical values. The effect of support conditions of the piping has been clarified by an example. The highly transient local stresses due to the temperature fluctuations in the mixing layer have been evaluated on the basis of measured inside wall surface temperatures. The measured fluid and wall temperature fluctuations have been compared. Also the effect of stress fluctuations on fatigue has been estimated. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 118
- Journal Issue
- 1
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 29-41
- ISSN
- 0029-5493
- CODEN
- NEDEA
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 21058790
- Subject category
- S42: ENGINEERING; S42: ENGINEERING;
- Descriptors DEI
- BENDING; FINITE ELEMENT METHOD; FLOW RATE; FLUCTUATIONS; HDR REACTOR; MOMENTUM TRANSFER; PIPES; STRATIFICATION; TEMPERATURE DEPENDENCE; TEMPERATURE DISTRIBUTION; THERMAL FATIGUE; THERMAL STRESSES
- Descriptors DEC
- BWR TYPE REACTORS; DEFORMATION; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FATIGUE; MECHANICAL PROPERTIES; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; STRESSES; THERMAL REACTORS; VARIATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS